ML20073T070

Reports Changes & Errors in ECCS Evaluation Models

ML20073T070
Person / Time
Site:	05000605
Issue date:	07/01/1994
From:	Recasha Mitchell GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MFN-088-94, MFN-88-94, NUDOCS 9407080148
Download: ML20073T070 (2)

Text

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.. , I GE Nuclear Encigy h1FN # 088-94 m OfEce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission hiail Station Pl-137 Washington, D C. 20555 Attention: Document Control Desk

Subject:

REPORTING OF CilANGES AND ERRORS IN ECCS ! \LUATh hiODELS Reference Letter, R.C. hiitchell to the OlEce of Nuclear Reactor I cgulation,

" Reporting of Changes and errors in ECCS Evaluation hiodels", dated June 30,1994 (h1FN # 090-93)

The purpose of this letter is to report, in accordance with 10CFRf JA6 (a)(3)(ii), the impact of changes and errors in the Emergency Core Cooling Syst ms (ECCS) evaluation methodology used by GE. This report covers the period from the last report (Reference) to the present, It is noted that Peak Cladding Temperature (PCT) variations resulting from plant spedric synern or fuel changes are not addressert in this letter. These should be trested, as appropriate, on a plant specific basis in accordance with other sections of 10 CFR 50.

There have been no changes or errors identified for the SAFE /REFLOOD model i described in NEDE 20566-P-A, " Analytical hiodel for Loss-of Coolant Analysis in Accordance with 10 CFR 50 Appendix K" There base been no chang s or errors identified for the S AFER/GESTR model described in NEDE 23785-1-P-A, "'I he GESTR-LOCA and S AFER hiodels for Evaluation of Loss-of-Coolai t Accidents", ans NEDE 30996-P-A, " SAFER hiodel far Evaluation of Loss-of-Coolant i,ccidents for Jet Pump and Non-Jet Pump Plants" By copy of this Ir.ter, Licensees utiliz ng the GE ECCS methodology in their plant licensing a e ir..'ormed of the status of changes in the evaluation methodology. Since no re analyr

s or technical specification modifications are required, this submittal is believed to i satisfy 10 CFR 50A6 (a)(3)(ii) for evaluation model changes without further reporting on I the part ofindividua! utilities.

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4 If you have any questions, please call me or 11 C. PfefTerlen at (408) 925 3392 Sincerels I $t, R.C. MitchellgManager Safety Evaluation Programs (408) 925 2755 Mail Code 487 cfr94/ hen cc: II.C. Pfefferlen